Nuclear fission



Yüklə 1,16 Mb.
səhifə18/26
tarix01.08.2018
ölçüsü1,16 Mb.
#65044
1   ...   14   15   16   17   18   19   20   21   ...   26

6.List of References


  1. ASAMPSA2, IRSN-PSN/RES/SAG 2013-0177, Best Practices guidelines for L2 PSA development and applications, Volume 1- General, April 2013.

  2. ASAMPSA2, IRSN-PSN/RES/SAG 2013-0177, Best Practices guidelines for L2 PSA development and applications, Volume 2- Best practices for the Gen II PWR, Gen II BWR L2 PSAs. Extension to Gen III reactors, April 2013.

  3. ASAMPSA2, IRSN-PSN/RES/SAG 2013-0177, Best Practices guidelines for L2 PSA development and applications, Volume 3- Extension to Gen IV reactors, April 2013.

  4. ASAMPSA_E, Report proposing the content of future L2 PSA guidance to be established within ASAMPSA_E, Technical report ASAMPSA_E / WP40 / D40.3 / 2015-11, IRSN/PSN-RES-SAG/15-00168

  5. U.S. NRC, An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events, NUREG/CR-6595, BNL-NUREG-52539, Rev.1, October, 2004.

  6. NUREG/CR-6906, “Containment Integrity Research at Sandia National Laboratories— An Overview,” by M. Hessheimer, Sandia National Laboratories, and R. A. Dameron, David Evans and Associates, Inc., July 2006.

  7. U.S. NRC Regulatory guide 1.216, Containment structural integrity evaluation for internal pressure loadings above design basis pressure, Revision 0, August 2010.

  8. UKEPR-0002-154 Issue 06, PCSR- Sub-chapter 15.4 –Level 2 PSA, 21-11-2012.

  9. IAEA SAFETY SERIES No. 50-P-8, "Procedures for Conducting Probabilistic Safety Assessment of Nuclear Power Plants (Level 2) – Accident Progression, Containment Analysis and Estimation of Accident Source Terms", 1995, ISBN 92-0-102195-X (superseded by IAEA SSG-4).

  10. IAEA SSG-4, Development and application of level 2 Probabilistic Safety Assessment for nuclear power plants, 2010.

  11. IAEA-TECDOC-1144, Probabilistic safety assessments of nuclear power plants for low power and shutdown modes, March 2000.

  12. Siu, N., Khericha, S., Conroy, S., Beck, S. and Blackman, H., Loss of Spent Fuel Pool Cooling: Model and Result, INL-96/0334, October 1996.

  13. U.S. Nuclear Regulatory Commission, "Technical Study of Spent Fuel Pool Accident Risk at Decommissioning Nuclear Power Plants," NUREG-1738, February 2001.

  14. U.S. Nuclear Regulatory Commission, "Reevaluation of Station Blackout Risk at Nuclear Power Plants Analysis of Loss of Offsite Power Events: 1986-2004," NUREG/CR-6890, December 2005.

  15. U.S. Nuclear Regulatory Commission, "Operating Experience Feedback Report-Assessment of Spent Fuel Cooling," NUREG-1275, Volume 12, February 1997.

  16. U.S. Nuclear Regulatory Commission, "Evaluation of External Hazards to Nuclear Power Plants in the United States," NUREG/CR-5042, December 1987.

  17. EPRI-3002000498 Spent Fuel Pool Risk Assessment Integration Framework (Mark-I and II BWR) and Pilot Plant Application, Palo Alto, CA 2013.

  18. F. C. Iglesias, C. E. L. Hunt, F. Garisto and D. S. Cox, Measured Release Kinetics of Ruthenium from Uranium Oxides in Air, Proc. Int’l. Seminar on Fission Product Transport Processes During Reactor Accidents, J. T. Rogers, editor, Hemisphere Publishing Corp., Washington, D. C., 1990.

  19. Z. Hózer, L. Matus, P. Windberg, CODEX and RUSET air oxidation experiments, Proc. 5th Technical seminar on the Phebus FP programme, Aix-en-Provence, France, June 24-26, 2003.

  20. Alvarez, R. et al, Reducing the hazards from stored spent power-reactor fuel in the United Stateş, Science and Global Security, Vol.11, pp.1-51, 2003.

  21. EPRI-3002002691, PWR Spent Fuel Pool Risk Assessment Integration Framework and Pilot Plant Application, Palo Alto, CA June 2014.

  22. Slovenian Nuclear Safety Administration, Slovenian national report on nuclear stress tests, Final Report, December 2011

  23. NUCLEAR REGULATORY COMMISSION, Evaluation of Potential Severe Accidents During Low Power and Shutdown Operation at Surry, Unit 1, Rep. NUREG/CR-6144, BNL-NUREG-52399, Washington, DC (1995).

  24. European Utility Requirements for LWR Nuclear Power Plants, Volume 2, Generic Nuclear Island Requirements, Chapter 17, PSA Methodology, Revision D, October 2012.

  25. A. Pulvirenti and M. Hiser, US NRC Technical letter report, Spent fuel pool criticality management spreadsheet: A compilation of the means used to meet sub-criticality requirements for all operating domestic spent fuel pools, public version, December 21, 2011.

  26. ASME/ANS RA-Sa-2009 Addenda to ASME/ANS RA-S-2008 Standard for Level 1 /Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, 2009.

  27. OECD, Nuclear Safety NEA/CSNI/R(2015)2, Status report on Spent fuel pool under loss of cooling and loss of coolant accident conditions, Final report, May 2015.

  28. Ibarra, J.G., et al., Operating experience feedback report: Assessment of spent fuel cooling, 1997, Report NUREG-1275, U.S. Nuclear Regulatory Commission, Washington, DC, USA.

  29. Sveriges Riksdag, Departementsserie 2012:18, Convention on nuclear safety 2012 extra ordinary meeting, Ds 2012:18, ISBN 978-91-38-23752-6.

  30. Sweden sixth national report under the Convention of Nuclear Safety, Ministry of the Environment, Ds 2013:56, Stockholm 2013.

  31. SSM, Swedish action plan for NPP, Response to ENSREG's request, Dec 2012

  32. EDG failed to start after undetected loss of two phases on 400 kV incoming offsite supply, 2013, Report IRS-8315, IAEA International Reporting System for Operating Experience, Vienna, Austria.

  33. Sweden’s fifth national report under the joint convention on the safety of spent fuel management and on the safety of radioactive waste management, Ds 2014:32, Stockholm Sweden.

  34. Relcon Scandpower report, confidential, analysis of severe accident sequences, 2008.

  35. Lloyd’s Register report, confidential, Methodology for Spent Fuel Pool (SFP) PSA, 2013.

  36. EPRI-3002003073, EPRI Sensitivity Analyses for Spent Fuel Pool Criticality, Palo Alto, December 2014, http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000003002003073

  37. U.S. Nuclear Regulatory Commission, Predictions of Spent Fuel Heatup After a Complete Loss of Spent Fuel Pool Coolant, NUREG 1726, June 2000, http://pbadupws.nrc.gov/docs/ML0037/ML003727905.pdf

  38. WESTINGHOUSE ELECTRIC COMPANY, Guidelines for Defining Plant Operating States, PA-RMSC-0279, WCAP-16749, Rev.0, May, 2007

  39. Lloyd’s Register report, confidential, Methodology for Level 1 Low Power and Shutdown PSA, 2013.

  40. Lloyd’s Register report, confidential, Methodology for Level 2 Low Power and Shutdown PSA, 2013.

  41. Lloyd’s Register report, confidential, Methodology for external fire, flooding and other external events, 2013.

  42. ANS/ASME-58.22-2014, Requirements for Low power and shutdown probabilistic risk assessment, trial, March 2015, USA.

  43. ASME/ANS RA-S-1.2-2014, Severe accident progression and radiological release (level 2) PRA standard for nuclear power plant applications for light water reactors (LWRs), trial-use standard, January 2015, USA.

  44. K. Sunnevik, Uppsala University and Lloyd’s Register Master thesis, Comparison of MAAP and MELCOR and evaluation of MELCOR as a deterministic tool within RASTEP, October 2014, Stockholm.

  45. P. Jacobsson et.al, PSAM 9, Shutdown PSA for Ringhals NPP Unit 3 Insight, overview and results, 2008.

  46. D. Jacquemain et.al, Nuclear Power Reactor Core Melt Accidents, IRSN 2015.

  47. Z. Kovacs, Low Power and Shutdown PSA for the Nuclear Power Plants with VVER440 type reactors, INTECH, September 2011.

  48. EPRI, Modular Accident Analysis Program 5 (MAAP5) applications guidance, Final report May 2015.

  49. Lloyd’s Register report, confidential, Guidance on methods for HRA, 2014.

  50. ASAMPSA_E guidance for level 2 PSA Volume 2 Implementing external Events modelling in Level 2 PSA, Technical report ASAMPSA_E/WP40/D40.7/2017-39 volume 2, Reference IRSN PSN/RES/SAG/2017-0002,

  51. ASAMPSA_E guidance for level 2 PSA Volume 3 , Verification and improvement of SAM strategies with L2 PSA, Technical report ASAMPSA_E/WP40/D40.7/2017-39 volume 3; Reference IRSN PSN/RES/SAG/2017-00001

  52. ASAMPSA_E D40.3, Report proposing the content of future L2 PSA guidance to be established within ASAMPSA_E, 2015

  53. Klein-Heßling W., Sonnenkalb M., Jacquemain D., Clément B., Raimond E., Dimmelmeier H., Azarian G., Ducros G., Journeau C., Herranz Puebla L.E., Schumm A., Miassoedov A., Kljenak I., Pascal G., Bechta S., Güntay S., Koch M.K., Ivanov I., Auvinen A. & Lindholm I., Conclusions on Severe Accident Research Priorities, Annals of Nuclear Energy, Vol.74, pp. 4-11, 2014

  54. B. Clément, R. Zeyen, The Objectives of the PHEBUS FP Experimental Program and Main Findings, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 4-10, 2013

  55. Herranz L.E., Haste T. & Karkela T., Major Advances in the Source Term Area within the European Severe Accident Research Network (SARNET2), Nuclear Engineering and Design, Vol. 288, pp. 56-74, 2015

  56. International Iodine Workshop, Marseille, March 2015, Full Proceedings, OECD/NEA/CSNI report, NEA/CSNI/R(2016)5, 2016

  57. Lewis B.J., Dickson R., Iglesias F.C., Ducros G. & Kudo T., Overview of experimental programs on core melt progression and fission product release behaviour, Journal of Nuclear Materials, Vol. 380, pp. 126–143, 2008

  58. Pontillon, Y., Ducros, G., Behaviour of fission products under severe PWR accident conditions: The VERCORS experimental programme - Part 2: Release and transport of fission gases and volatile fission products, Nuclear Engineering and Design, Vol. 240 (7), pp. 1853-1866, 2010

  59. Grégoire A.C. & Haste T., Material Release from the Bundle in Phebus FP, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 63-74, 2013

  60. Marchetto C., Brillant G., Plumecocq W., Fission Product Release from Nuclear Fuel I. Physical Modeling in the ASTEC code, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 88-95, 2013

  61. Marchetto C., Brillant G., Plumecocq W., Fission Product Release from Nuclear Fuel II. Validation of ASTEC/ELSA on Analytical and Large Scale Experiments, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 96-101, 2013

  62. Gallais-During, A., Bonnin, J., Malgouyres, P.-P., Morin, S., Bernard, S., Gleizes, B., Pontillon, Y., Hanus, E. & Ducros, G., Performance and first results of fission product release and transport provided by the VERDON facility, Nuclear Engineering and Design, Vol. 277, pp. 117-123, 2014

  63. Girault N. & Payot. F., Insights into the Iodine behavior and Speciation in the Phébus Primary Circuit, Special Issue of Annals of Nuclear Energy, Vol. 61, pp.143-156, 2013

  64. Gouello M., Mutelle H., Cousin F., Sobanska S. & Blanquet E., Analysis of the Iodine Gas Phase Produced by Interaction of CsI and MoO3 Vapour in Flowing Steam, Nuclear Engineering and Design, Vol. 263, pp. 462-472, 2013

  65. Grégoire A.C., Kalilainen J., Cousin F., Mutelle H., Cantrel L., Auvinen A., Haste T. & Sobanska S., Role of Molybdenum on Iodine Transport in the RCS in Nuclear Severe Accident Conditions, Annals of Nuclear Energy, Vol. 78, pp. 117-129, 2015

  66. Cousin F., Kissane M. & Girault N., Modeling of Fission Product Transport in the Reactor Coolant System, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 135-142, 2013

  67. Cantrel L., Cousin F., Bosland L., Chevalier-Jabet K. & Marchetto C., ASTEC V2 Severe Accident Integral Code : Fission Product Modelling and Validation, Nuclear Engineering and Design, Vol. 272, pp. 195-206, 2014

  68. Cantrel L., Louis F. & Cousin F., Advances in Mechanistic Understanding of Iodine Bahaviour in Phébus FP tests with the Help of Ab-initio Calculations, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 170-178, 2013

  69. Xerri B., Canneaux S., Louis F., Trincal J., Cousin F., Badawi M. & Cantrel L., Ab-Initio Calculations and Iodine Kinetic Modelling in the Reactor Coolant System of a Pressurized Water Reactor in Case of Severe Nuclear Accident, Computational and Theoretical Chemistry, Vol. 990, pp. 194-208, 2012

  70. Badawi M., Xerri B., Canneaux S., Cantrel L. & Louis F., Molecular Structures and Thermodynamic Properties of 12 Gaseous Cesium-Containing Species of Nuclear Safety Interest: Cs 2, CsH, CsO,
    Cs 2O, CsX, and Cs 2X 2 (X = OH, Cl, Br, and I), Journal of Nuclear Materials, Volume 420, Issue 1-3, pp. 452-462, 2012

  71. Šulková K., Federi

  72. J., Louis F., Cantrel L., Demovi

  73. L. & Černušák I., Thermochemistry of Small Iodine Species, Physica Scripta, Vol. 88, 058304, 2013

  74. Sudolská M., Cantrel L. & Černušák I., Microhydration of Caesium Compounds Cs, CsOH, CsI and Cs2I2 Complexes with One to Three H2O Molecules. Modelling for PWR Reactor, Journal of Molecular Modelling, Vol. 20(4), N°2218, 2014

  75. Sulkova K., Cantrel L. & Louis F., Gas-phase Reactivity of Cesium-Containing Species by Quantum Chemistry, J. Phys. Chem A, vol. 119(35), pp. 9373-9384, 2015

  76. Karkela T., Ver N., Haste T., Davidovich N., Pyykonen J. & Cantrel L., Transport of Ruthenium in Primary Circuit Conditions during a Severe NPP Accident, Annals of Nuclear Energy, Vol. 74, pp. 173-183, 2014

  77. Miradji F., Souvi S., Cantrel L., Louis F. & Vallet V., Thermodynamic Properties of Gaseous Ruthenium Species, Journal of Physical Chemistry A, 119(20), pp. 4961-4971, 2015

  78. Miradji, F., Virot, F., Souvi, S., Cantrel, L., Louis, F. & Vallet, V., Thermochemistry of Ruthenium Oxyhydroxide Species and Their Impact on Volatile Speciations in Severe Nuclear Accident Conditions, Journal of Physical Chemistry A, Vol. 120 (4), pp. 606-614, 2016

  79. Bottomley P.D.W., Van-Winkle S., Knebel K., Haste T., Souvi S.M.O, Auvinen A. Kalilainen J. & Karkela T., Revaporisation of Fission Product Deposits in the Primary Circuit and its Impact on Accident Source Term, Annals of Nuclear Energy, Vol. 74, pp. 208-223, 2014

  80. Girault N., Simondi-Teisseire B., Payot F. & Clément B., Iodine Behaviour in the Containment in Phébus FP, Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 157-169, 2013

  81. Haste T., Payot F., Manenc C., Clément B., March P., Simondi-Teisseire B. & Zeyen R., Phébus FPT3: Overview of Main Results Concerning the Behaviour of Fission Products and Structural Materials in the Containment, Nuclear Engineering and Design, vol. 261, pp. 333-346, 2013

  82. Glowa G.A., Auvinen A., Bosland L., Dickinson S., Herranz L.E., Kim H.C., Lamminmaki S., Karkela T., Powers D., Salay M. & Tietze S., Iodine-Paint Interactions during nuclear Reactor Severe Accidents, Annals of Nuclear Energy, Vol. 74, pp. 184-199, 2014

  83. Dickinson S., Auvinen A., Ammar Y., Bosland L., Clément B., Funke F., Glowa G., Karkela T., Powers D., Tietze S., Weber G. & Zhang S., Experimental and Modelling Studies of Iodine Oxide Formation and Aerosol Behaviour Relevant to Nuclear Reactor Accidents, Annals of Nuclear Energy, Vol. 74, pp. 200-207, 2014

  84. Glowa, G.A., Moore, C.J. & Ball, J.M., The main outcomes of the OECD Behaviour of Iodine (BIP) Project, Annals of Nuclear Energy, Vol. 61, pp. 179-189, 2013

  85. Gupta, S., Schmidt, E., Von Laufenberg, B., Freitag, M., Poss, G., Funke, F. & Weber, G., THAI test facility for experimental research on hydrogen and fission product behaviour in light water reactor containments, Nuclear Engineering and Design, Vol. 294, pp. 183-201, 2015

  86. Clément, B. & Simondi-Teissiere, B., STEM: An IRSN project on source term evaluation and mitigation, Proc. Transactions of the American Nuclear Society - ANS Annual Meeting, Las Vegas, NV, U.S., November 7-11th, Vol. 103, pp. 475-476, 2010

  87. Chevalier-Jabet K., Cousin F., Cantrel L. & Seropian C., Source Term Assessment with ASTEC and Associated Uncertainty Analysis using SUNSET Tool, Nuclear Engineering and Design, Vol. 272, pp. 207-218, 2014

  88. OECD/NEA/CSNI Report on Filtered Containment Venting Systems, NEA/CSNI/R(2014)7, 2014

  89. Trincal J., Cantrel L., Cousin F., Fevre-Nollet V. & Lebegue P., Impact of Atmospheric Species Reactivity on Radioactive Gaseous Iodine Transport in Severe Accident Conditions, WIT Transactions on Ecology and the Environment, vol. 198, pp. 77-86, 2015

  90. Raimond E., Clément B., Denis J. & Vola D., Use of PHEBUS FP and other FP Programs Atmospheric Radioactive Release Assessment in case of a Severe Accident in a PWR (Deterministic and Probabilistic Approaches Developed at IRSN), Special Issue of Annals of Nuclear Energy, Vol. 61, pp. 190-198, 2013

  91. Patrick Chatelard et al., “Overview of the independent ASTEC V2.0 validation by SARNET partners”, Nuclear Engineering and Design 272 (2014) 136-151.

  92. MELCOR Computer Code Manuals, Vol. 1: Primer and Users’ Guide, Version 2.1.6840, SAND 2015-6691 R, Sandia National Laboratories, August 2015.

  93. MELCOR Computer Code Manuals, Vol. 2: Reference Manual, Version 2.1.6840, SAND 2015-6692 R, Sandia National Laboratories, August 2015.

  94. MELCOR Computer Code Manuals, Vol. 3: MELCOR Assessment Problems, Version 2.1.7347, SAND 2015-6693 R, Sandia National Laboratories, August 2015. http://melcor.sandia.gov/

  95. Symbolic Nuclear Analysis Package (SNAP), 2007, User’s Manual. Applied Programming Technology, Inc. Bloomsburg, PA.

  96. Larry Humphries, MELCOR Code Development Status, 7th meeting of the “European MELCOR User Group”, BEL V, Tractebel Engineering, Brussels, Belgium, march 17-18, 2015.

  97. ROMANIA - National Action Plan post-Fukushima, Revision 1, December 2014.

  98. Joakim Klug and Francesco Di Dedda, Lloyd’s Register Consulting, Protection from the potential release of radioactive materials, Article in Nuclear Connect publication, page 24, January 2016.

  99. Atomic Energy Society of Japan, A Standard for Procedure of Seismic Probabilistic Risk Assessment for Nuclear Power Plants: 2015 (in Japanese)

  100. A. Yamaguchi, S. Nakamura, et al., Revision of the AESJ Standard for Seismic Probabilistic Risk Assessment (3) Fragility Evaluation, PSAM 12, 2014

  101. Status Report on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions Report NEA/CSNI/R(2015)2

  102. Characterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident Report NUREG/CR-7143, USNRC

  103. Separate-effect tests on zirconium cladding degradation in air ingress situations C. Duriez et al. Nuclear Engineering and Design, Vol. 239, pp. 244–253, 2009

  104. High-Temperature Oxidation of Zircaloy-4 in Oxygen-Nitrogen Mixtures M. Steinbrück, S. Schäffer Oxidation of Metals, in Press (available on-line), 2015

  105. Modelling of Zircaloy-4 Accelerated Degradation Kinetics in Nitrogen-Oxygen Mixtures at 850°C M. Lasserre et al. Journal of Nuclear Materials, Vol. 462, pp. 221-229, 2015

  106. Qualitative Analysis of Zircaloy-4 Cladding Air Degradation in O2-N2 Mixtures at High Temperature M. Lasserre et al. Materials and Corrosion, Vol. 65(3), pp. 250-259, 2014

  107. Synthesis of the VERCORS experimental program: Separate-effect experiments on Fission Product release, in support of the PHEBUS-FP program G. Ducros, Y. Pontillon, P.P. Malgouyres Annals of Nuclear Energy, 61, pp. 75-87, 2013

  108. Outcome of VEGA program on radionuclide release from irradiated fuel under severe accident conditions A. Hidaka Journal of Nuclear Science and Technology, 48 (1), pp. 85–102, 2011

  109. Fission-Product release during transient heating of irradiated CANDU fuel Z. Liu et al. Nuclear Technology, 131, pp. 22–35, 2000

  110. Synthesis of Spent Fuel Pool Accident Assessments using Severe Accident Codes J. Fleurot et al. Annals of Nuclear Energy, Vol.74, pp. 58-71, 2014

  111. A new research program on accidents in spent fuel pools: the DENOPI project H. Mutelle et al. Proceedings of WRFPM 2014 Sendai, Japan, Sept. 14-17, 2014

  112. J. Vitazkova, E. Cazzoli - Probabilistic Safety Assessment KKM Shutdown Internal Floods, September 2010.

  113. Petya Vryashkova, Pavlin Groudev, Antoaneta Stefanova, Investigation of oxygen depletion during hydrogen recombination for VVER 1000 of Kozlofuy NPP, NENE 2013, September 9-12, Bled, Slovenia, 2013.

  114. A.E. Stefanova, P.P. Groudev, B.P. Atanasova, Assessment of passive autocatalytic recombiners’ capabilities in case of Zr oxidation during station blackout scenario for TVSA and TVSM fuel assemblies of VVER 1000, Progress in Nuclear Energy, vol. 51 (2009), pp. 582–588.

  115. A.E. Stefanova, P.P. Groudev, B.P. Atanasova., Comparison of hydrogen generation for TVSM and TVSA fuel assemblies for water energy reactor (VVER)-1000, Nuclear Engineering and Design, vol. 239 (2009), pp. 180–186.

  116. P. Groudev, A. Stefanova, P. Vryashkova, MELCOR study of VVER-1000 behavior in case of overheated reactor core quenching, ICONE22, Prague, Czech Republic, July 7-11, 2014.

  117. Kaliopa Mancheva, Kiril Tzenkov, Evgeny Borisov, Main aspects and results of level 2 PSA for KNPP VVER-1000/B320, Proceedings of the 10th International conference on nuclear option in countries with small and medium electricity grids, Zadar, Croatia, 1-4 June, 2014.

  118. Kaliopa Mancheva, Kiril Tzenkov, Evgeny Borisov, Severe accident phenomena assessment for VVER-1000(V320) spent fuel pool, Presentation on Bulatom conference 2015, Traditional international nuclear conference, Bulgarian nuclear energy – national, regional and word energy security, 3th-5th June, 2015.

  119. BNRA, Republic of Bulgaria, Fifth National Report on Fulfillment of the Obligations on the Joint Convention on the Safety of Spent Fuel management and on Safety of Radioactive Waste Management, Sofia, September 2014.

  120. NRA, Analysis of the TEPCO Fukushima Daiichi NPS Accident Interim Report, Oct., 2014

  121. IAEA-TECDOC-1722, Review of Seismic Evaluation Methodologies for Nuclear Power Plants Based on a Benchmark Exercise, 2013

  122. Y. Toyoda, N. Tanaka, et al., Numerical Simulation for Overflow Behavior of Water from Spent Fuel Pool with Sloshing in the 2007 Niigata-ken Chuetsu-Oki Earthquake, CRIEPI Report

  123. Bareith, A., Elter, J., Siklossy, T., Karsa, Z., 2014, “External Events PSA for the spent fuel pool of the Paks NPP” Proceedings of the 12th International Conference on Probabilistic Safety Assessment and Management, External Events Hazard/PRA Modeling for Nuclear Power Plants II, Honolulu, Hawaii, USA, PSAM12.

  124. MELCOR Computer Code Manuals. Reference Manuals. Version 1.8.5 December 2000, NUREG/CR-6119, Vol. 2, Rev. 2. SAND2000-2417/1.

  125. OECD, Status Report on Hydrogen Management and Related Computer Codes, NEA/CSNI/R(2014)8, 26-Jun-2014.

  126. Hydrogen flammability data and application to PWR loss-of-coolant accident». WAPD-SC-545. Operated for the U.S. Atomic Energy Commission by Westinghouse Electric Corporation. Dr.Z.M. Shapiro, T.R. Moffette. 1957.

  127. Flame Acceleration And Deflagration-to-Detonation Transition In Nuclear Safety. State-of-the-Art Report. NEA/CSNI/R(2000)7. August 2000.

  128. The VULCANO VE-U7 Corium spreading benchmark. Christophe Journeau at al., Progress in Nuclear Energy 48 (2006) 215–234.

  129. In-Soo Ye at al., Numerical investigation of the spreading and heat transfer characteristics of Ex-vessel core melt., Nuclear Engineering and Technology, Vol 45 No 1, 2013.

  130. ASAMPSA_E, D30.2, Lesson of Fukushima Dai-ichi accident for PSA, 2015.

  131. Fast-running Code for an Extended PSA Source Term Prognosis in Case of Severe Accidents, PSAM 13, 2016.

  132. US NRC, Technical study of spent fuel pool accident risk at decommissioning nuclear power plants, October 2000.

  133. Meyer, L., et al., Overview of Containment Issues and Major Experimental Activities, the First European Review Meeting on Severe Accident Research (ERMSAR-2005), Aix-en-Provence, France, 2005 November 14-16.

  134. Grimm, P., et al. Parametric studies on the reactivity of spent fuel storage pools, 1984. In: Fifth International Meeting on Thermal Nuclear Reactor Safety, September 9-13, 1984, Karlsruhe, Germany: Nuclear Research Center Karlsruhe, KfK 3880/1, Vol. 1, pp. 626-633.

  135. Cojazzi G. et.al, Benchmark exercise on expert judgment techniques in PSA Level 2, https://cordis.europa.eu/pub/fp5-euratom/docs/21-beejt.pdf

  136. S. Basu, JM. Bonnet, D. Vola, M. Cranga, M. T. Farmer, F. Robledo, C.Splenger Learnings from 30 Years of R&D on Molten Core Concrete Interaction NUTHOS-11, Gyeongju, Korea, October 9-13, 2016.

  137. Meignen et al., Status of steam explosion understanding and modelling Annals of Nuclear Energy, Volume 74, December 2014, Pages 125-133

  138. G. Pohlner et al., Analyses on ex-vessel debris formation and coolability in SARNET frame. Annals of Nuclear Energy, Volume 74, December 2014, Pages 50-57



Yüklə 1,16 Mb.

Dostları ilə paylaş:
1   ...   14   15   16   17   18   19   20   21   ...   26



Verilənlər bazası müəlliflik hüququ ilə müdafiə olunur ©muhaz.org 2024
rəhbərliyinə müraciət
gir | qeydiyyatdan keç
    Ana səhifə
Dərs
Dərslik
Guide
Kompozisiya
Mücərrəd
Mühazirə
Qaydalar
Referat
Report
Request
Review

yükləyin